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Fuel cycle analysis in a thorium fueled reactor using bidirectional fuel movement : correction to report MIT-2073-1, MITNE-51
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1965], 1965)
This report corrects an error discovered in the code used in the study "Fuel Cycle Analysis in a Thorium Fueled Reactor Using Bidirectional Fuel Movement," MIT-2073-1, MITNE-51. The results of the correction show considerable ...
LMFBR Blanket Physics Project progress report no. 2
(Cambridge, Mass., Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1971], 1971)
LMFBR Blanket Physics Project progress report no. 3
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1972], 1972)
LMFBR Blanket Physics Project progress report no. 4
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1973], 1973)
LMFBR Blanket Physics Project progress report no. 7
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1970], 1970)
Heavy water lattice project annual report / editors: T.J. Thompson ... [et al.] ; contributors J. Barch ... [et al.]
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1965], 1965)
Analysis of strategies for improving uranium utilization in pressurized water reactors
(Cambridge, Mass. : Massachusetts Institute of Technology, Energy Laboratory, 1981, 1981)
Systematic procedures have been devised and applied to evaluate core design and fuel management strategies for improving uranium utilization in Pressurized Water Reactors operated on a once-through fuel cycle. A principal ...
Studies of epithermal neutrons in uranium, heavy water lattices
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1964, 1964)
Measurements related to reactor physics parameters were made in three heavy water lattices. The three lattices studied consisted of 0.250-inch-diameter, 1.03 w/o U2 3 5 uranium fuel rods arranged in triangular arrays and ...
Transient heat transfer induced pressure fluctuations in the fuel coolant interaction
(Cambridge, Mass. : Massachusetts Institute of Technology. Dept. of Nuclear Engineering, 1973, 1973)
Assessment of thorium blankets for fast breeder reactors
(Cambridge, Mass. : Massachusetts Institute of Technology. Dept. of Nuclear Engineering, 1973, 1973)